Seismic Strength Evaluation of Corroded Reactor Containment Building

Abstract The purpose of this study is to investigate the effects of the corrosion phenomenon on the seismic strength of a reactor containment building (RCB) in nuclear power plants (NPPs). A corrosion degradation model is proposed based on the rationale of NPP structures and applied to the reinforce...

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Main Authors: Md Samdani Azad, Duy-Duan Nguyen, Bidhek Thusa, Tae-Hyung Lee
Format: Article
Language:English
Published: SpringerOpen 2025-01-01
Series:International Journal of Concrete Structures and Materials
Subjects:
Online Access:https://doi.org/10.1186/s40069-024-00734-4
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author Md Samdani Azad
Duy-Duan Nguyen
Bidhek Thusa
Tae-Hyung Lee
author_facet Md Samdani Azad
Duy-Duan Nguyen
Bidhek Thusa
Tae-Hyung Lee
author_sort Md Samdani Azad
collection DOAJ
description Abstract The purpose of this study is to investigate the effects of the corrosion phenomenon on the seismic strength of a reactor containment building (RCB) in nuclear power plants (NPPs). A corrosion degradation model is proposed based on the rationale of NPP structures and applied to the reinforcements near the base mat of RCB. Three corrosion levels associated with the service life of the structure up to 60 years are considered in this study. Seven different cases are considered depending on the location of corrosion. A series of pushover analyses are performed to evaluate the seismic responses of the corroded RCB, considering all cases with different levels of damage due to corrosion. The results are obtained in terms of global responses, in which capacity curves, base shear at different limit states, demand–capacity ratios, and reserve strength ratios (RSR) are quantified. The findings of this study demonstrate that corrosion can cause a reduction in structural capacity in terms of base shear of up to 19.5% during its service life of 60 years and that is dependent on how the corrosion is propagated within RCB. The results also illustrate that corrosion in the elements in the tension zone increases the sensitivity of the responses subjected to seismic loads.
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institution Kabale University
issn 2234-1315
language English
publishDate 2025-01-01
publisher SpringerOpen
record_format Article
series International Journal of Concrete Structures and Materials
spelling doaj-art-e7f69c60f17546d59ebfef51d9ff28052025-01-19T12:14:34ZengSpringerOpenInternational Journal of Concrete Structures and Materials2234-13152025-01-0119111410.1186/s40069-024-00734-4Seismic Strength Evaluation of Corroded Reactor Containment BuildingMd Samdani Azad0Duy-Duan Nguyen1Bidhek Thusa2Tae-Hyung Lee3Department of Civil and Environmental Engineering, Yonsei UniversityDepartment of Civil Engineering, Vinh UniversityDepartment of Civil and Environmental Engineering, Hanbat National UniversityDepartment of Civil and Environmental Engineering, Konkuk UniversityAbstract The purpose of this study is to investigate the effects of the corrosion phenomenon on the seismic strength of a reactor containment building (RCB) in nuclear power plants (NPPs). A corrosion degradation model is proposed based on the rationale of NPP structures and applied to the reinforcements near the base mat of RCB. Three corrosion levels associated with the service life of the structure up to 60 years are considered in this study. Seven different cases are considered depending on the location of corrosion. A series of pushover analyses are performed to evaluate the seismic responses of the corroded RCB, considering all cases with different levels of damage due to corrosion. The results are obtained in terms of global responses, in which capacity curves, base shear at different limit states, demand–capacity ratios, and reserve strength ratios (RSR) are quantified. The findings of this study demonstrate that corrosion can cause a reduction in structural capacity in terms of base shear of up to 19.5% during its service life of 60 years and that is dependent on how the corrosion is propagated within RCB. The results also illustrate that corrosion in the elements in the tension zone increases the sensitivity of the responses subjected to seismic loads.https://doi.org/10.1186/s40069-024-00734-4Reactor containment buildingBeam–truss modelCorrosionPushover analysisDemand–capacity ratioReserve strength ratio
spellingShingle Md Samdani Azad
Duy-Duan Nguyen
Bidhek Thusa
Tae-Hyung Lee
Seismic Strength Evaluation of Corroded Reactor Containment Building
International Journal of Concrete Structures and Materials
Reactor containment building
Beam–truss model
Corrosion
Pushover analysis
Demand–capacity ratio
Reserve strength ratio
title Seismic Strength Evaluation of Corroded Reactor Containment Building
title_full Seismic Strength Evaluation of Corroded Reactor Containment Building
title_fullStr Seismic Strength Evaluation of Corroded Reactor Containment Building
title_full_unstemmed Seismic Strength Evaluation of Corroded Reactor Containment Building
title_short Seismic Strength Evaluation of Corroded Reactor Containment Building
title_sort seismic strength evaluation of corroded reactor containment building
topic Reactor containment building
Beam–truss model
Corrosion
Pushover analysis
Demand–capacity ratio
Reserve strength ratio
url https://doi.org/10.1186/s40069-024-00734-4
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AT duyduannguyen seismicstrengthevaluationofcorrodedreactorcontainmentbuilding
AT bidhekthusa seismicstrengthevaluationofcorrodedreactorcontainmentbuilding
AT taehyunglee seismicstrengthevaluationofcorrodedreactorcontainmentbuilding